1. NAME AND TITLE
ARMYL-N: Calculation of Transmission Factors for Neutrons from Nuclear Explosions.
Department of Theoretical Studies, Central Armaments Laboratory, Arcueil, French Ministry
of Defense through the OECD NEA Data Bank, Gif-sur-Yvette, France.
3. CODING LANGUAGE AND COMPUTER
FORTRAN IV; UNIVAC 1106.
4. NATURE OF PROBLEM SOLVED
ARMYL-N calculates the variation of the neutron dose transmission factor as a function of the
thickness of flat shields of concrete, steel, or earth, for radiations occurring as a result of nuclear
5. METHOD OF SOLUTION
Invariant imbedding is used in ARMYL-N.
6. RESTRICTIONS OR LIMITATIONS
ARMYL-N is bound by the following limits:
Maximum number of energy groups - 10
Maximum number of angular groups - 7
There is no restriction on range.
7. TYPICAL RUNNING TIME
ARMYL-N uses 4 minutes on a UNIVAC 1108 for a maximum number of energy and angular
8. COMPUTER HARDWARE REQUIREMENTS
ARMYL-N runs on a UNIVAC 1106 with 51 K words of 36 bits, 2 mag tape units for
auxiliary storage and an on-line printer.
9. COMPUTER SOFTWARE REQUIREMENTS
A FORTRAN IV compiler is required.
M. Marquie, "Neutron Dose Transmission Factors in Various Shields," ORNL-tr-4280, a
translation of LCA 74 R 130, ETUDE 07.1, No. 283/DET (October 1974).
11. CONTENTS OF CODE PACKAGE
Included are the referenced document and one (1.2MB) DOS diskette which contains the source
codes and sample problem input and output.
12. DATE OF ABSTRACT
KEYWORDS: INVARIANT IMBEDDING; NEUTRON; ONE-DIMENSION; SLAB; WEAPONS RADIATION